ML20083J548
| ML20083J548 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood, 05000000 |
| Issue date: | 12/27/1983 |
| From: | Tramm J, Tramm T COMMONWEALTH EDISON CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.3.01, TASK-TM NUDOCS 8401100193 | |
| Download: ML20083J548 (1) | |
Text
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Commonwealth Edison
[O N) one First Nation 11 Plaza Chicino. Ilonois
(
~7 Address Reply to: Post Office Box 767 (j Chicago. Illinois 60690 December 27, 1983 Mr. Harold R.
Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Byron Generating Station Units 1 and 2 Braidwood Generating Station Units 1 and 2 Automatic PORV Isolation NRC Dockets 50-454/455 and 50-456/457
Dear Mr. Denton:
This is to provide additional information regarding NUREG-0737 Item II.K,3.1, " Isolation and Testing of Automatic Power-Operated Reliek Valve Isolation System".
NRC review of this information should close out Confirmatory Issuc. 28 with regard to the issue of automatic PORV block valve actuation.
As indicated in Section E.49 of Appendix E to the Byron /Braidwood FSAR, the need for autoclosure of PORV block valves has been reviewed as part of a Westinghouse Owner's Group effort.
The report on this effort, WCAP-9804, has been provided to the NRC.
The study demonstrated that such a plant modification should not be made.
The study was intended to cover all Westinghouse plants, including Byron and Braidwood.
Our review of the underlying assumptions made in this study indicates that it is indeed applicable to the Byron /Braidwood design.
We conclude that automatic PORV isolation is unnecessary for these plants.
Please address further questions regarding this matter to this office.
One (1) signed original and fifteen (15) copies of this letter are provided for NRC review.
Very truly yours,
/Nr 4W T.
R.
Tramm Nuclear Licensing Administrator 8401100193 831227
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